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Title: Independent safety evaluation of the CR562 (CR6) control rod test

Abstract

This report documents the Independent Safety Evaluation performed for the CR562 control rod. CR562 is a reference Series II control rod which has been designated as an experiment (CR-6) since post- irradiation examination has been planned as part of the surveillance program for FFTF control rods. Prior analysis as an experiment has not been required since the test operated within the Technical Specification Limits up to this time. The control rod will be operated beyond the Technical Specification fluence limit during the last 30 days of Cycle 10B. A TDD-1A has been written to support this extension, and this ISE documents the independent review. A similar procedure was used for the CR544 control rod. 9 refs.

Authors:
Publication Date:
Research Org.:
Westinghouse Hanford Co., Richland, WA (United States)
OSTI Identifier:
719397
Report Number(s):
WHC-SP-0403
ON: TI89020250
DOE Contract Number:
AC06-87RL10930
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1988
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CONTROL ELEMENTS; PERFORMANCE TESTING; FFTF REACTOR; REACTOR SAFETY; HEAT TRANSFER; HYDRAULICS; POST-IRRADIATION EXAMINATION; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; SYSTEM FAILURE ANALYSIS

Citation Formats

Van Keuren, J.C. Independent safety evaluation of the CR562 (CR6) control rod test. United States: N. p., 1988. Web.
Van Keuren, J.C. Independent safety evaluation of the CR562 (CR6) control rod test. United States.
Van Keuren, J.C. 1988. "Independent safety evaluation of the CR562 (CR6) control rod test". United States. doi:.
@article{osti_719397,
title = {Independent safety evaluation of the CR562 (CR6) control rod test},
author = {Van Keuren, J.C.},
abstractNote = {This report documents the Independent Safety Evaluation performed for the CR562 control rod. CR562 is a reference Series II control rod which has been designated as an experiment (CR-6) since post- irradiation examination has been planned as part of the surveillance program for FFTF control rods. Prior analysis as an experiment has not been required since the test operated within the Technical Specification Limits up to this time. The control rod will be operated beyond the Technical Specification fluence limit during the last 30 days of Cycle 10B. A TDD-1A has been written to support this extension, and this ISE documents the independent review. A similar procedure was used for the CR544 control rod. 9 refs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1988,
month =
}

Technical Report:
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